ML19221A003
| ML19221A003 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/31/1976 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| GQL-1250, NUDOCS 7905160479 | |
| Download: ML19221A003 (2) | |
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e, Your letter of Jtily 12, 1976 requested additional infor:ation evaluating the adequacy of the reacter pressure vessel suppcrts under loads not previcusly censidered. Since that tine, we have =e vith cther racccer L.c.,ccx,,eco users., an e.,.,crt to eva.,uate the concern and e,, -.
.i discuss pcssible resolutions.
'2We paths are being pursued in parallel to determine cur required actica.
'~he first apprcach is to undertake a review cf veri spenscred by a grcup cf utilities evaluating the absolute and relative probability of a pcst,ulated pipe break between the reacter vessel ncccie and the reactor cavity vall.
Science Applications, Inc. (SAI) is subnitting their results in the fcr= cf a tepical report in late August, 1976. The :iEC staff was introduced to the study in a presentation involving SAI cn vu y.;, _yi6.
Tne secccd approach is a review cf the additional infer ation requested in ycur July 12, Ic76 letter which requires a ecstly, nulti-year snal.vsis for each ;,lant.
Discussicts vitb Habecck & 'Jilecx and cther censulting firms, review of ACES hearings transcripts, and your letter itself indicates uncertainties in the present state-of-the-art analysis to evaluate thic particula' case.
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